ML21193A369

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Final Written Examination and Operating Test Outlines (Folder 3)
ML21193A369
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 06/16/2021
From:
NRC Region 1
To:
Exelon Generation Co
Shared Package
ML20261H327 List:
References
EPID L-2021-OLL-0028
Download: ML21193A369 (21)
v • d • e


Text

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Calvert Cliffs Nuclear Power Plant Date of Examination: 6/6/2021 Exam Level: RO Operating Test #: 2021 Administrative Topic Type Describe activity to be performed (see Note) Code*

Calculate BAST volume required to raise RWT to refueling boron Conduct of Operations R, M concentration G2.1.20 Ability to interpret and execute procedure steps. (RO-4.6)

Determine Power Ratio Recorder Potentiometer setting with the plant computer failed Conduct of Operations R, N G2.1.7 Ability to evaluate plant performance and make operational judgements based on operating characteristics, reactor behavior, and instrument interpretation. (RO-4.4)

Determine requirements and dose limits associated with performance of Radiation Control R, D a task in the RCA G2.3.7 Ability to comply with radiation work permit requirements during normal or abnormal conditions. (RO-3.5)

Respond to Condenser Vacuum reduction (Evaluate U-2 Load versus Vacuum)

Equipment Control R, D G2.2.44 Ability to interpret control room indications to verify the status and operation of a system and understand how operator actions and directives affect plant and system conditions. (RO-4.2)

NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics, when all 5 are required.

  • Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes) [2]

(N)ew or (M)odified from bank ( 1) [2]

(P)revious 2 exams ( 1; randomly selected) [0]

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Calvert Cliffs Nuclear Power Plant Date of Examination: 6/6/2021 Exam Level: RO Operating Test #: 2021 Control Room Systems:

  • 8 for RO; 7 for SRO-I; 2 or 3 for SRO-U Safety System / JPM Title Type Code*

Function

a. SIM-1 Respond to a charging header rupture 004 Chemical and Volume Control System A, N 1 A4.08 Charging (RO-3.8/SRO-3.4)
b. SIM-2 Align a LPSI Pump for Core Flush 006 Emergency Core Cooling System A, D, EN, L 2 A4.07 ECCS pumps and valves (RO-4.4/SRO-4.4)
c. SIM-3 Override Shut a PORV 010 Pressurizer Pressure Control System A, D, L 3 A4.03 PORV and block valves (RO-4.0/SRO-3.8)
d. SIM-4 Respond to a loss of Secondary Pumps 056 Condensate System A, N 4S A2.04 Loss of condensate pumps (RO-2.6/SRO-2.8)
e. SIM-5 Shift 13 IRU Power Supply 027 Containment Iodine Removal System (CIRS) D, EN 5 A4.01 CIRS controls (RO-3.3/SRO-3.3)
f. SIM-6 Perform Vital Auxiliaries 062 AC Electrical Distribution System N, L 6 A4.01 All Breakers (RO-3.3/SRO-3.1)
g. SIM-7 Reactor Protection System Test 012 Reactor Protection System N 7 A4.04 Bistables, trips, reset and test switches (RO-3.3/SRO-3.3)
h. SIM-8 Shift Component Cooling Heat Exchangers 008 Component Cooling Water System D 8 A4.01 CCW indications and controls (RO-3.3/SRO-3.1)

In-Plant Systems

  • 3 for RO; 3 for SRO-I; 3 or 2 for SRO-U
a. PLT-1 Start 11 & 12 Containment Air Coolers 022 Containment Cooling System D, E, R 5 A4.01 CCS Fans (RO-3.6/SRO-3.6)
b. PLT-2 Respond to a fire on site 086 Fire Protection System (FPS) N 8 AA4.05 Deluge Valves (RO-3.0/SRO-3.5)
c. PLT-3 Control RCS and S/G Inventory from 2C43 035 Steam Generator System D, E 4P A3.01 S/G Water Level Control (RO-4.0/SRO-3.9)

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2

  • All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
  • Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 [4]

(C)ontrol room (D)irect from bank 9 / 8 / 4 [6]

(E)mergency or abnormal in-plant 1 / 1 / 1 [2]

(EN)gineered safety feature 1 / 1 / 1 (control room system) [2]

(L)ow-Power / Shutdown 1 / 1 / 1 [3]

(N)ew or (M)odified from bank including 1(A) 2 / 2 / 1 [5 including 2(A)]

(P)revious 2 exams 3 / 3 / 2 (randomly selected) [0]

(R)CA 1 / 1 / 1 [1]

(S)imulator

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Calvert Cliffs Nuclear Power Plant Date of Examination: 6/6/2021 Exam Level: SRO-I Operating Test #: 2021 Administrative Topic Type Describe activity to be performed (see Note) Code*

Determine Operator Qualifications Conduct of Operations R, N G2.1.8 Ability to coordinate personnel activities outside the control room. (SRO-4.1)

Review and approve a completed Surveillance Test Procedure Conduct of Operations R, D G2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation. (SRO-4.7)

Establish Initial Conditions for STP O-8A-1 Equipment Control R, D G2.2.12 Knowledge of surveillance procedures. (SRO-4.1)

Review and Authorize KI Radiation Control R, N G2.3.14 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities. (SRO-3.8)

Recommend Protective Action Guidelines to Public Officials Emergency Plan R, D G2.4.44 Knowledge of emergency plan protective action recommendations (SRO-4.4)

NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics, when all 5 are required.

  • Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes) [3]

(N)ew or (M)odified from bank ( 1) [2]

(P)revious 2 exams ( 1; randomly selected) [0]

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Calvert Cliffs Nuclear Power Plant Date of Examination: 6/6/2021 Exam Level: SRO-I Operating Test #: 2021 Control Room Systems:

  • 8 for RO; 7 for SRO-I; 2 or 3 for SRO-U Safety System / JPM Title Type Code*

Function

a. SIM-1 Respond to a charging header rupture 004 Chemical and Volume Control System A, N 1 A4.08 Charging (RO-3.8/SRO-3.4)
b. SIM-2 Align a LPSI Pump for Core Flush 006 Emergency Core Cooling System A, D, EN, L 2 A4.07 ECCS pumps and valves (RO-4.4/SRO-4.4)
c. SIM-3 Override Shut a PORV 010 Pressurizer Pressure Control System A, D, L 3 A4.03 PORV and block valves (RO-4.0/SRO-3.8)
d. SIM-4 Respond to a loss of Secondary Pumps 056 Condensate System A, N 4S A2.04 Loss of condensate pumps (RO-2.6/SRO-2.8)
e. SIM-5 Shift 13 IRU Power Supply 027 Containment Iodine Removal System (CIRS) D, EN 5 A4.01 CIRS controls (RO-3.3/SRO-3.3)
f. SIM-6 Perform Vital Auxiliaries 062 AC Electrical Distribution System N, L 6 A4.01 All Breakers (RO-3.3/SRO-3.1)
g. SIM-8 Shift Component Cooling Heat Exchangers 008 Component Cooling Water System D 8 A4.01 CCW indications and controls (RO-3.3/SRO-3.1)

In-Plant Systems

  • 3 for RO; 3 for SRO-I; 3 or 2 for SRO-U
a. PLT-1 Start 11 & 12 Containment Air Coolers 022 Containment Cooling System D, E, R 5 A4.01 CCS Fans (RO-3.6/SRO-3.6)
b. PLT-2 Respond to a fire on site 086 Fire Protection System (FPS) N 8 AA4.05 Deluge Valves (RO-3.0/SRO-3.5)
c. PLT-3 Control RCS and S/G Inventory from 2C43 035 Steam Generator System D, E 4P A3.01 S/G Water Level Control (RO-4.0/SRO-3.9)

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2

  • All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
  • Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 [4]

(C)ontrol room (D)irect from bank 9 / 8 / 4 [6]

(E)mergency or abnormal in-plant 1 / 1 / 1 [2]

(EN)gineered safety feature 1 / 1 / 1 (control room system) [2]

(L)ow-Power / Shutdown 1 / 1 / 1 [3]

(N)ew or (M)odified from bank including 1(A) 2 / 2 / 1 [4 including 2(A)]

(P)revious 2 exams 3 / 3 / 2 (randomly selected) [0]

(R)CA 1 / 1 / 1 [1]

(S)imulator

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Calvert Cliffs Nuclear Power Plant Date of Examination: 6/6/2021 Exam Level: SRO-U Operating Test #: 2021 Administrative Topic Type Describe activity to be performed (see Note) Code*

Determine Operator Qualifications Conduct of Operations R, N G2.1.8 Ability to coordinate personnel activities outside the control room. (SRO-4.1)

Review and approve a completed Surveillance Test Procedure Conduct of Operations R, D G2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation. (SRO-4.7)

Establish Initial Conditions for STP O-8A-1 Equipment Control R, D G2.2.12 Knowledge of surveillance procedures. (SRO-4.1)

Review and Authorize KI Radiation Control R, N G2.3.14 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities. (SRO-3.8)

Recommend Protective Action Guidelines to Public Officials Emergency Plan R, D G2.4.44 Knowledge of emergency plan protective action recommendations (SRO-4.4)

NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics, when all 5 are required.

  • Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes) [3]

(N)ew or (M)odified from bank ( 1) [2]

(P)revious 2 exams ( 1; randomly selected) [0]

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Calvert Cliffs Nuclear Power Plant Date of Examination: 6/6/2021 Exam Level: SRO-U Operating Test #: 2021 Control Room Systems:

  • 8 for RO; 7 for SRO-I; 2 or 3 for SRO-U Safety System / JPM Title Type Code*

Function

a. SIM-1 Respond to a charging header rupture 004 Chemical and Volume Control System A, N 1 A4.08 Charging (RO-3.8/SRO-3.4)
b. SIM-2 Align a LPSI Pump for Core Flush 006 Emergency Core Cooling System A, D, EN, L 2 A4.07 ECCS pumps and valves (RO-4.4/SRO-4.4)
c. SIM-6 Perform Vital Auxiliaries 062 AC Electrical Distribution System N, L 6 A4.01 All Breakers (RO-3.3/SRO-3.1)

In-Plant Systems

  • 3 for RO; 3 for SRO-I; 3 or 2 for SRO-U
a. PLT-1 Start 11 & 12 Containment Air Coolers 022 Containment Cooling System D, E, R 5 A4.01 CCS Fans (RO-3.6/SRO-3.6)
b. PLT-2 Respond to a fire on site 086 Fire Protection System (FPS) N 8 AA4.05 Deluge Valves (RO-3.0/SRO-3.5)
  • All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
  • Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 [2]

(C)ontrol room (D)irect from bank 9 / 8 / 4 [2]

(E)mergency or abnormal in-plant 1 / 1 / 1 [1]

(EN)gineered safety feature 1 / 1 / 1 (control room system) [1]

(L)ow-Power / Shutdown 1 / 1 / 1 [2]

(N)ew or (M)odified from bank including 1(A) 2 / 2 / 1 [3 including 1(A)]

(P)revious 2 exams 3 / 3 / 2 (randomly selected) [0]

(R)CA 1 / 1 / 1 [1]

(S)imulator

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #2 OP-Test # 2021 Examiners: Operators:

Initial Conditions: Unit-1 is at 100% power, MOC. Unit-2 is at 100% power.

Turnover: 13 Component Cooling Pump is OOS.

Instructions to the crew: The Shift Manager directs the crew to commence equalizing RCS boron per OI-1H Section 6.6 to support activities scheduled next shift.

Critical Tasks:

1. Trips the reactor within 1 minute of the PROT CH TRIP alarm.
2. Commences a rapid RCS Cooldown not to exceed 100°F in any one hour.
3. Commences OTCC when both S/G levels are below (-)350 inches and prior to CET temperatures reaching 560°F after Heat Removal capability has been lost.

Event # Malfunction # Event Type* Event Description 1 N/A N-ATC/SRO Commence Boron Equalization / OI-1H I-ATC/SRO 2 rcs026_01 LT-110X Fails Low T-SRO C-BOP/SRO 3 1-CC-273 11 CCW Pump Leak / AOP-7C T-SRO C-BOP/SRO 4 cd001 Loss of Condenser Vacuum / AOP-7G R-ATC rps005 ATWS 5 C-ATC/SRO rps006 EOP-0 6 swyd002 C-ALL Loss of Offsite Power AFW Suction Line Block 7 1-AFW-161 M-ALL Loss of All Feedwater / EOP-3

  • (N)ormal (R)eactivity (I)nstrument (C)omponent (M)ajor (T)ech Spec

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #3 OP-Test # 2021 Examiners: Operators:

Initial Conditions: Unit-1 is at 100% power, MOC. Unit-2 is at 100% power.

Turnover: 13 Condensate Booster Pump is OOS.

Instructions to the crew: The Shift Manager directs the crew to shift Charging Pumps by starting 12 and securing 11 Charging Pump per OI-2A Section 6.2 to support activities scheduled next shift.

Critical Tasks:

1. Trip 11A & 12B RCPs or 11B & 12A RCPs when RCS pressure decreases to <1725 PSIA prior to RCS pressure going below 1300 PSIA.
2. Establishes at least one train of High-Pressure Safety Injection flow to the RCS within 15 minutes of the SIAS auto failure.
3. Identifies 12 Steam Generator as faulted and isolates 12 S/G within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

Event # Malfunction # Event Type* Event Description 1 N/A N-ATC/SRO Shift Charging Pumps / OI-2A I-BOP/SRO 2 ms019_03 12 S/G LT1123C Fails Low T-SRO C-ALL 3 rcs003 RCS Leak Inside Containment / AOP-2A T-SRO U25-11-LCL- C-BOP/SRO 4 Transformer Loss of Cooling / AOP-7E BKR R-ATC LOCA 5 rcs002 M-ALL EOP-0 esfa001_01 6 C-ATC/SRO SIAS Auto Failure esfa001_02 12 S/G Steam Line Rupture Outside Containment 7 ms016_09 M-ALL EOP-8

  • (N)ormal (R)eactivity (I)nstrument (C)omponent (M)ajor (T)ech Spec

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #4 OP-Test # 2021 Examiners: Operators:

Initial Conditions: Unit-1 is at 50% power, MOC. Unit-2 is at 100% power.

Turnover: 12 Boric Acid Pump and 13 Component Cooling Pump are OOS.

Instructions to the crew: The Shift Manager directs the crew to lower reactor power and stabilize at 45% per OP-3 to support activities scheduled next shift.

Critical Tasks

1. Establishes AFW flow to at least one S/G prior to S/G levels going below (-)350 inches.
2. Identifies 11 S/G as the ruptured SG and isolates 11 S/G within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of the reactor trip.
3. Trips all RCPs within 15 minutes of violating the RCP NPSH pump curve.

Event # Malfunction # Event Type* Event Description N-BOP/SRO 1 N/A Lower Reactor Power R-ATC I-BOP/SRO 2 rcs024_04 RCS Pressure PT-102D Fails Low T-SRO C-ALL 3 480v002_01 Loss of MCC-104 / AOP-7I T-SRO 4 cd008 C-ALL Condensate Header Rupture / AOP-3G EOP-0 5 ms002_01 M-ALL SGTR (2 tubes) in 11 SG P1C01 6 C-BOP/SRO Generator Field/Exciter Breakers Fail to Open EXDISC 7 125v001_02 M-ALL Loss of 12 DC Bus / EOP-8

  • (N)ormal (R)eactivity (I)nstrument (C)omponent (M)ajor (T)ech Spec

ES-401 PWR Examination Outline Form ES-401-2 Facility: Calvert Cliffs Date of Exam: June 2021 RO K/A Category Points SRO-Only Points Tier Group K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* Total A2 G* Total

1. 1 3 3 3 3 3 3 18 3 3 6 Emergency and Abnormal Plant 2 1 1 2 N/A 2 2 N/A 1 9 2 2 4 Evolutions Tier Totals 4 4 5 5 5 4 27 5 5 10 1 3 3 3 2 3 2 3 3 2 2 2 28 3 2 5 2.

Plant 2 1 0 1 1 1 1 1 1 1 1 1 10 0 2 1 3 Systems Tier Totals 4 3 4 3 4 3 4 4 3 3 3 38 5 3 8

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 2 2 3 3 2 2 1 2 Note: 1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outline sections (i.e., except for one category in Tier 3 of the SRO-only section, the Tier Totals in each K/A category shall not be less than two). (One Tier 3 radiation control K/A is allowed if it is replaced by a K/A from another Tier 3 category.)
2. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points, and the SRO-only exam must total 25 points.
3. Systems/evolutions within each group are identified on the outline. Systems or evolutions that do not apply at the facility should be deleted with justification. Operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.
4. Select topics from as many systems and evolutions as possible. Sample every system or evolution in the group before selecting a second topic for any system or evolution.
5. Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
6. Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.
7. The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable K/As.
8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics IRs for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above. If fuel-handling equipment is sampled in a category other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2. (Note 1 does not apply). Use duplicate pages for RO and SRO-only exams.
9. For Tier 3, select topics from Section 2 of the K/A catalog and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.

G* Generic K/As

  • These systems/evolutions must be included as part of the sample (as applicable to the facility) when Revision 3 of the K/A catalog is used to develop the sample plan. They are not required to be included when using earlier revisions of the K/A catalog.
    • These systems/evolutions may be eliminated from the sample (as applicable to the facility) when Revision 3 of the K/A catalog is used to develop the sample plan.

ES-401 2 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 1 (RO/SRO)

E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G* K/A Topic(s) IR #

000007 (EPE 7; BW E02&E10; CE E02) 6 Occurrence of a reactor trip 4.3 1 Reactor Trip, Stabilization, Recovery / 1 000008 (APE 8) Pressurizer Vapor Space 2 Sensors and detectors 2.7 2 Accident / 3 Knowledge of operational implications of EOP 000009 (EPE 9) Small Break LOCA / 3 2.4.20 warnings, cautions and notes. 3.8 3 000015 (APE 15) Reactor Coolant Pump 7 RCP seals 2.9 4 Malfunctions / 4 000025 (APE 25) Loss of Residual Heat 1 Loss of RHRS during all modes of operation 3.9 5 Removal System / 4 000026 (APE 26) Loss of Component 2 Loads on the CCWS in the control room 3.2 6 Cooling Water / 8 000027 (APE 27) Pressurizer Pressure 3 Controllers and positioners 2.6 7 Control System Malfunction / 3 000029 (EPE 29) Anticipated Transient 1 Reactor nuclear instrumentation 4.4 8 Without Scram / 1 Ability to recognize abnormal indications for 000038 (EPE 38) Steam Generator Tube 2.4.4 system operating parameters that are entry-level 4.5 9 Rupture / 3 conditions for emergency and abnormal operating procedures.

000055 (EPE 55) Station Blackout / 6 1 Effect of battery discharge rates on capacity 3.3 10 000056 (APE 56) Loss of Offsite Power / 6 6 Safety injection pump 3.6 11 Actions contained in EOP for loss of vital ac 000057 (APE 57) Loss of Vital AC 1 electrical instrument bus 4.1 12 Instrument Bus / 6 000058 (APE 58) Loss of DC Power / 6 3 Vital and battery bus components 3.1 13 000062 (APE 62) Loss of Nuclear Service 1 Location of a leak in the SWS 2.9 14 Water / 4 Ability to interpret control room indications to 000065 (APE 65) Loss of Instrument Air / 8 2.2.44 verify the status and operation of a system and 4.2 15 understand how operator actions and directives affect plant and system conditions.

000077 (APE 77) Generator Voltage and 2 Over-excitation 3.3 16 Electric Grid Disturbances / 6 000040 (APE 40; BW E05; CE E05; W E12) 3 Manipulation of controls required to obtain 3.8 17 Steam Line RuptureExcessive Heat desired operating results during abnormal, and Transfer / 4 emergency situations.

000054 (APE 54; CE E06) Loss of Main 2 Normal, abnormal and emergency operating 3.2 18 Feedwater /4 procedures associated with Loss of Feedwater Ability to evaluate plant performance and make 000011 (EPE 11) Large Break LOCA / 3 2.1.7 operational judgments based on operating 4.7 76 characteristics, reactor behavior and instrument interpretation.

Charging pump problems 000022 (APE 22) Loss of Reactor Coolant 2 3.7 77 Makeup / 2 Ability to use plant computer to evaluate system 000026 (APE 26) Loss of Component 2.1.19 or component status. 3.8 78 Cooling Water / 8 Ability to determine and interpret the following as Loss of Salt Water 2 they apply to the Loss of Salt Water: Salt Water 3.0 79 pump problems

ES-401 3 Form ES-401-2 Knowledge of the purpose and function of major 000057 (APE 57) Loss of Vital AC 2.1.28 system components and controls. 4.1 80 Instrument Bus / 6 000029 (EPE 29) Anticipated Transient 7 Reactor trip breaker indicating lights 4.3 81 Without Scram / 1 K/A Category Totals: 3 3 3 3 3/3 3/3 Group Point Total: 18/6

ES-401 4 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 2 (RO/SRO)

E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G* K/A Topic(s) IR #

000005 (APE 5) Inoperable/Stuck Control Rod / 1 3 Required actions if more than one 3.5 19 rod is stuck or inoperable 000028 (APE 28) Pressurizer (PZR) Level Control 2 Relationships between PZR 2.9 20 Malfunction / 2 pressure increase and reactor makeup/letdown imbalance 1 Radiation exposure hazards 3.5 21 000036 (APE 36; BW/A08) Fuel-Handling Incidents / 8 00051 (APE 51) Loss of Condenser Vacuum / 4 1 Loss of steam dump capability 2.8 22 upon loss of condenser vacuum 000059 (APE 59) Accidental Liquid Radwaste Release / 9 2 The permit for liquid radioactive- 2.9 23 waste release 000067 (APE 67) Plant Fire On Site / 8 5 Plant and control room ventilation 3.0 24 systems 000069 (APE 69; W E14) Loss of Containment Integrity / 5 1 Isolation valves, dampers and 3.5 25 electropneumatic devices.

000076 (APE 76) High Reactor Coolant Activity / 9 1 Process radiation monitors 2.6 26 (CE A16) Excess RCS Leakage / 2 2.4.9 Knowledge of low 3.8 27 power/shutdown implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies 000003 (APE 3) Dropped Control Rod / 1 2.2.22 Knowledge of limiting conditions 4.7 82 for operations and safety limits.

000032 (APE 32) Loss of Source Range Nuclear 6 Confirmation of reactor trip 4.1 83 Instrumentation / 7 000061 (APE 61) Area Radiation Monitoring System Alarms 6 Required actions if alarm channel 4.1 84

/7 is out of service (CE E09) Functional Recovery 2.4.18 Knowledge of the specific bases 4.0 85 for EOPs.

K/A Category Point Totals: 1 1 2 2 2/2 1/2 Group Point Total: 9/4

ES-401 5 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 1 (RO/SRO)

System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* K/A Topic(s) IR #

003 (SF4P RCP) Reactor Coolant 5 RCP seal leakage detection 3.1 28 Pump instrumentation 004 (SF1; SF2 CVCS) Chemical and 6 RCS temperature and pressure 3.4 29 Volume Control Failure modes for pressure, flow, pump 005 (SF4P RHR) Residual Heat 1 motor amps, motor temperature and tank 2.7 30 Removal level instrumentation 005 (SF4P RHR) Residual Heat 3 RCS pressure boundary motor-operated 2.7 31 Removal valves Avoidance of thermal and pressure 006 (SF2; SF3 ECCS) Emergency 1 stresses due to pump startup 3.1 32 Core Cooling 007 (SF5 PRTS) Pressurizer 2.4.46 Ability to verify that the alarms are 4.2 33 Relief/Quench Tank consistent with the plant conditions.

008 (SF8 CCW) Component Cooling 2 CCW pump, including emergency backup 3.0 34 Water 010 (SF3 PZR PCS) Pressurizer 1 Pressure detection systems 2.7 35 Pressure Control 012 (SF7 RPS) Reactor Protection 1 Trip setpoint adjustment 2.9 36 012 (SF7 RPS) Reactor Protection 1 CRDS 3.9 37 013 (SF2 ESFAS) Engineered 1 Definitions of safety train and ESF 2.8 38 Safety Features Actuation channel 013 (SF2 ESFAS) Engineered 2 Safety system logic and reliability 2.9 39 Safety Features Actuation 022 (SF5 CCS) Containment Cooling 1 Containment cooling fans 3.0 40 026 (SF5 CSS) Containment Spray 5 Containment spray reset switches 3.5 41 026 (SF5 CSS) Containment Spray 2 Recirculation spray system 4.2 42 039 (SF4S MSS) Main and Reheat 4 Malfunctioning steam dump 3.4 43 Steam 059 (SF4S MFW) Main Feedwater 3 Power level restrictions for operation of 2.7 44 MFW pumps and valves 059 (SF4S MFW) Main Feedwater 2 AFW system 3.4 45 061 (SF4S AFW) 1 Relationship between AFW flow and RCS 3.6 46 Auxiliary/Emergency Feedwater heat transfer 062 (SF6 ED AC) AC Electrical 5 Methods for energizing a dead bus 2.9 47 Distribution 062 (SF6 ED AC) AC Electrical 3 Interlocks between automatic bus transfer 2.8 48 Distribution and breakers 063 (SF6 ED DC) DC Electrical 3 Battery charger and battery 2.9 49 Distribution 064 (SF6 EDG) Emergency Diesel 8 Fuel oil storage tanks 3.2 50 Generator 073 (SF7 PRM) Process Radiation 1 Release termination when radiation 4.0 51 Monitoring exceeds setpoint 076 (SF4S SW) Service Water 2.1.27 Knowledge of system purpose and or 3.9 52 function.

ES-401 6 Form ES-401-2 078 (SF8 IAS) Instrument Air 1 Air pressure 3.1 53 078 (SF8 IAS) Instrument Air 4 Cooling water to compressor 2.6 54 103 (SF5 CNT) Containment 1 Containment isolation 3.9 55 004 (SF1; SF2 CVCS) Chemical and 12 CIAS, SIAS 4.3 86 Volume Control 013 (SF2 ESFAS) Engineered 6 Inadvertent ESFAS actuation 4.0 87 Safety Features Actuation Knowledge of the emergency action level 063 (SF6 ED DC) DC Electrical 2.4.41 thresholds and classifications. 4.6 88 Distribution Ability to explain and apply all system 076 (SF4S SW) Service Water 2.1.32 limits and precautions. 4.0 89 103 (SF5 CNT) Containment 2 Necessary plant conditions for work in 3.2 90 containment K/A Category Point Totals: 3 3 3 2 3 2 3 3/3 2 2 2/2 Group Point Total: 28/5

ES-401 7 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 2 (RO/SRO)

System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* K/A Topic(s) IR #

002 (SF2; SF4P RCS) Reactor 13 Core exit thermocouples 3.4 56 Coolant 015 (SF7 NI) Nuclear 3 Component interconnections 2.6 57 Instrumentation 017 (SF7 ITM) In-Core Temperature 1 Natural circulation indications 3.5 58 Monitor 033 (SF8 SFPCS) Spent Fuel Pool 1 Maintenance of spent fuel level 2.9 59 Cooling 034 (SF8 FHS) Fuel-Handling 2 Dropped cask 3.4 60 Equipment 035 (SF 4P SG) Steam Generator 1 S/G water level control 4.0 61 055 (SF4S CARS) Condenser Air 2.1.30 Ability to locate and operate components, 4.4 62 Removal including local controls.

071 (SF9 WGS) Waste Gas 4 Relationship of hydrogen/oxygen 2.5 63 Disposal concentrations to flammability 072 (SF7 ARM) Area Radiation 3 Fuel building isolation 3.6 64 Monitoring 011 (SF2 PZR LCS) Pressurizer 5 Letdown flow controller 3.2 65 Level Control 014 (SF1 RPI) Rod Position 4 Misaligned Rod 3.9 91 Indication 045 (SF 4S MTG) Main Turbine 15 Turbine overspeed 2.6 92 Generator 075 (SF8 CW) Circulating Water 2.4.45 Ability to prioritize and interpret the 4.3 93 significance of each annunciator or alarm.

K/A Category Point Totals: 1 0 1 1 1 1 1 1/2 1 1 1/1 Group Point Total: 10/3

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Calvert Cliffs Date of Exam: 2021 Category K/A # Topic RO SRO-only IR # IR #

Knowledge of administrative requirements for temporary 2.1.15 management directives such as standing orders, night orders, 2.7 66 Operations memos, etc.

Ability to locate and use procedures related to shift 2.1.5 staffing, such as minimum crew complement, overtime 2.9 67 limitations, etc.

1. Conduct of Operations Knowledge of the refueling processes 2.1.41 3.7 94 2.1.8 Ability to coordinate personnel activities outside the control 4.1 95 room.

Subtotal 2 2 Ability to determine operability and/or availability of safety 2.2.37 related equipment 3.6 68 Knowledge of the process for making changes to procedures 2.2.6 3.0 69

2. Equipment Control Knowledge of the process for managing troubleshooting 2.2.20 activities. 3.8 96 Knowledge of conditions and limitations in the facility license.

2.2.38 4.5 97 Subtotal 2 2 Knowledge of radiological safety principles pertaining to 2.3.12 licensed operator duties 3.2 70 2.3.15 Knowledge of radiation monitoring systems 2.9 71

3. Radiation 2.3.4 Knowledge of radiation exposure limits under normal or 3.2 72 emergency conditions.

Control 2.3.6 Ability to approve release permits. 3.8 98 Subtotal 3 1 2.4.19 Knowledge of EOP layout, symbols and icons. 3.4 73 2.4.3 Ability to identify post-accident instrumentation. 3.7 74 Ability to verify system alarm setpoints and operate controls 2.4.50 identified in the alarm response manual. 4.2 75

4. Emergency Procedures/Plan Knowledge of general operating crew responsibilities during 2.4.12 emergency operations. 4.3 99 Knowledge of the Emergency Plan 2.4.29 4.4 100 Subtotal 3 2 Tier 3 Point Total 10 7

ES-401 Record of Rejected K/As Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected K/A Rejected Emergency and Abnormal Plant Evolutions associated solely with Babcock and Wilcox (BW) reactors -

Calvert Cliffs is a CE design.

Rejected 025 (SF5 ICE) Ice Condenser - Calvert Cliffs does not have an ice condenser installed.

Rejected 033 Loss of Intermediate Range Nuclear Instrumentation. Calvert Cliffs does not have Intermediate Range NIs 1/1 SRO Question #79: Added Loss of Salt Water to the Tier 1, Group 1 list of E/APEs to be available for random selection in accordance with ES-401 Attachment 1. Loss of Salt Water was randomly selected for Question 79.

2/1 073, K4.02 Calvert Cliffs does not have a letdown isolation on a high RCS activity. Randomly reselected K4.01 RO Question #51 2/2 002, A1.12 Calvert Cliffs does not vent CRDS. Randomly reselected A1.13 RO Question #56 3 2.4.11 Knowledge of abnormal condition procedures is tested extensively throughout the operating test. This K/A is SRO Question considered oversampled.

  1. 100 Randomly reselected 2.4.29

ES-401 Record of Rejected K/As Form ES-401-4

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